study of the behavior of structural materials under irradiation (temperature range from 320 to 1000°C, damage doses up to 200dpa);

investigations of the BOR-60 neutronic characteristics;

accumulation of radionuclides.

Promising Areas of Research

investigation of the performance and behavior under irradiation of structural, absorbing and fuel materials from various types of reactors (power, research, propulsion, space, etc.) under conditions simulating their operational modes (stationary and transient) as well as under the design-basis accident conditions;

development of techniques and devices for tests, including instrumented ones, of fuel, absorbing and structural materials for new-generation nuclear facilities;